开式自然循环系统出口排热管内流型演化研究

开式自然循环系统作为新型非能动余排系统最终热阱排放回路,其安全稳定运行对于事故工况下堆芯余热安全导出至关重要,本研究通过可视化实验方法观察了开式自然循环系统出口排热管内流型演化特性,发现随着加热功率增加,开式自然循环逐步建立,该系统出口排热管内依次出现单相流、间歇性汽泡流、弥散泡状流、弹状流和间歇喷射流5种典型流型,分析了出口排热管内流型与系统稳定运行之间的关系,发现了开式自然循环系统剧烈振荡的根源,为提高开式自然循环系统流动稳定性提供了参考。     

低干度自然循环两相流动系统的静态分岔特性

基于一维两相四方程漂移流模型,采用数值模拟的方法对5MW低温核供热堆热工模拟回路（HTRL-5）的自然循环进行模拟,分析在自然循环系统中存在的分岔特性及其参数效应。结果表明：在一定条件下低干度自然循环两相流动系统存在静态分岔现象,并且静态分岔点出现在特征曲线的切点上;当压力高到一定程度或热流密度小到一定程度系统的分岔点消失。     

低压下两相自然循环流动不稳定性的实验研究──（Ⅱ）影响因素的研究

通过对低压下不同工况系统实验研究，总结了包括系统压力、进口过冷度、加热段进出口阻力、加热段管径等对流动不稳定的影响，并对实验数据进行了综合，得出了一个无量纲关系式。     

低压下两相自然循环流动不稳定性的实验研究──（Ⅰ）机理探索

对两相自然循环流动不稳定性问题进行了机理性实验研究,系统压力范围为０．１ＭＰａ－０．４ＭＰａ。通过实验,分析了不稳定流动的机理,并根据其内在特性总结出两类主要的不稳定流动,为深入进行理论研究打下了良好基础。     

HRTL-5自然循环稳态特性

基于一维两相四方程漂移流模型,采用数值模拟的方法对5MW低温核供热堆热工水力模拟回路（HRTL-5）的自然循环稳态特性进行模拟,分析了HRTL-5自然循环流量特性及其参数效应。结果表明：1)漂移流模型比均相流模型更适用于HRTL-5;2)当系统压力为1.5MPa时,系统自然循环流量随加热热流密度的升高而增加;3)当系统压力为0.5MPa时,系统自然循环流量随加热热流密度的升高先增加后减小;4)自然循环流量随加热段入口欠热度的升高而减小;5)当加热热流密度较低时,〖JP3〗系统自然循环流量随压力的升高而减小,当加热热流密度较高时,系统自然循环流量随压力的变化呈现复杂状况。     

Advances on the research on nonlinear phenomena in boiling natural circulation loop

The state-of-the-art of theoretical investigations on the flow oscillations that occur in a boiling natural circulation loop has been presented here. Motivation behind the work is to develop a high-fidelity model that is capable of predicting nature of flow instabilities more accurately. At the low pressures and low heat fluxes conditions, the major four types of instabilities may occur in boiling natural circulation loop depending on operating conditions: Flow excursion, Geysering instability, Flashing-induced instability and Type I density-wave oscillations. The characteristics of different instabilities as well as the effects of different operating and geometric parameters on them have been reviewed. The objective of this review is to gather the research findings on the nonlinear stability phenomena in various boiling flow channel systems over a period of several years. This review indicates that most of the theoretical predictions of amplitudes and periods of the sustained oscillations are carried out using two models, namely, homogeneous equilibrium model (HEM) (still debatable) and drift-flux model (DFM) (more realistic) and are validated by experimental findings. This review work on theoretical investigations presented in this paper indicates that there are enough scopes for improving mathematical formulations of the natural circulation boiling loop (NCBL) for thermohydraulic instabilities.     

自然循环系统摇摆条件下棒束通道内传热特性研究

棒束燃料元件子通道间流体存在搅混与横向二次流,流动及阻力特性相较矩形通道、圆管等简单通道更为复杂。核动力舰船、船舶、小型浮动核电站等会受到海浪影响,经常处于倾斜、摇摆、垂荡等瞬变运动下。目前的相关研究多集中在低压工况的研究领域,高温高压自然循环运动条件下的研究较少。本文采用实验研究方法,对自然循环系统摇摆条件下棒束通道内流动传热特性进行了研究,获得了过冷沸腾和饱和沸腾两种条件下摇摆角度和摇摆周期对棒束壁面温度变化和传热系数的影响,并获得了摇摆周期内棒束通道内的传热系数计算关系式。结果表明,饱和沸腾传热系数变化比过冷沸腾的剧烈;在本文实验工况范围内,棒表面传热系数波动幅值随着摇摆幅度的增大而增大;摇摆条件下棒束通道过冷沸腾和饱和沸腾工况时均传热系数基本不变。     

基于RELAP5的ERVC两相自然循环能力研究

利用RELAP5程序建立压力容器外部冷却（ERVC）系统模型,在水淹平衡条件下分析不同的安全壳内压力、冷却水过冷度、加热功率和水淹水位对系统两相自然流动能力的影响,找到各工况下的临界过冷度和不稳定性边界。结果表明：AP1000的ERVC系统设计具有很大裕量,仅依靠自然循环就可通过下封头对熔池进行有效冷却;安全壳内压力越高、冷却水过冷度越低、加热功率越大、水淹水位越高,两相自然循环流量越高。但当加热功率水平较低时,压力对临界过冷度影响不大;冷却水过冷度低于临界值时,会发生剧烈的倒流和流量震荡现象;当水淹水位低于5.5 m时,不能建立稳定的两相自然循环流动。     

自然循环流动阻力系统特性研究

研究了闭式自然循环实验回路单相流动阻力的系统特性。结果表明：在本文的实验参数范围内，以一维充分发展强迫流动关系式为基础的计算结果与实验结果相比有一定的偏离，这与ＲＦＬＡＰ５／ＭＯＤ２程序对ＬＳＴＦ等装置及ＤｏｅｌＰｌａｎｔ的分析结果基本一致。建立了自然循环流动阻力系统特性的归一化分析数学模型对实验数据进行归一化分析，得到了一组新的自然循环系统等效摩擦阻力系数的经验关系式。本文较大地拓宽了该基础研究领域的实验数据范围，从系统的角度确证了自然循环与强制流动存在的差别并分析其机理成因，结论可供先进反应堆的研究和设计参考。     

C型换热器管外流体两相自然循环数值模拟

建立了简化的C型换热器管外流体CFD分析模型,模拟了反应堆安全壳内置换料水箱（IRWST）中典型气液两相自然循环特性。首先用公开发表文献中的试验数据对计算方法进行校验,计算中采用的湍流模型、壁面沸腾模型等能较好地捕捉主流流体升温特性、两相自然循环特性。结果表明：C型换热器增加了管外流体流场分布的不均匀性,提高了冷、热流体间的搅混强度,有助于降低管外流体温度差,增加大容积水池内的自然循环能力;但由于壁面对气泡的阻滞作用,换热器弯管及水平管局部区域空泡份额最大,发生了气泡聚集。计算结果可为非能动余热排出换热器的设计提供支持。     

Characteristics of Type-I Density Wave Oscillations in a Natural Circulation BWR at Relatively High Pressure

Experiments were conducted to investigate two-phase flow instabilities in a boiling natural circulation loop with a chimney at high pressure. The SIRIUS-N facility was designed to have non-dimensional values which are nearly equal to those of a typical natural circulation BWR. The observed oscillations are found to be density wave oscillations, since the void fractions in the chimney inlet and exit are out of phase. They belong to the Type-I category, since they occur at low flow qualities, according to the Fukuda—Kobori's classification. Moreover, the oscillation period correlates well with the passing time of bubbles in the chimney section regardless of the system pressure, the heat flux, and the inlet subcooling. Two distinct phenomena are found in relation between the oscillation period and liquid passing time in the chimney, indicating that the driving mechanisms of the instabilities are different between low and high pressures. Stability maps were obtained in reference to the inlet subcooling and the heat flux at the system pressures of 1, 2, 4, and 7.2 MPa. The flow became stable below a certain heat flux regardless of the channel inlet subcooling. The stable region enlarges with increasing system pressure. Thus, the stability margin becomes larger in a startup process of a reactor by pressurizing the reactor sufficiently before withdrawing the control rods. The obtained stability map demonstrates that the nominal operating condition of the ESBWR has a significant stability margin to the unstable region.     

Effect of Liquid Density Differences on Boiling Two-Phase Flow Stability

In order to investigate the effect of considering liquid density dependence on local fluid temperature in the thermal-hydraulic stability, a linear stability analysis is performed for a boiling natural circulation loop with an adiabatic riser. Type-I and Type-II instabilities were to investigate according to Fukuda-Kobori's classification. Type-I instability is dominant when the flow quality is low, while Type-II instability is relevant at high flow quality. Type-II instability is well known as the typical density wave oscillation. Neglecting liquid density differences yields estimates of Type-II instability margins that are too small, due to both a change in system-dynamics features and in the operational point. On the other hand, neglecting liquid density differences yields estimates of Type-I stability margins that are too large, especially due to a change in the operational point. Neglecting density differences is thus non-conservative in this case. Therefore, it is highly recommended to include liquid density dependence on the fluid subcooling in the stability analysis if a flow loop with an adiabatic riser is operated under the condition of low flow quality.     

自然循环蒸汽发生器倒U型管内倒流特性的无量纲分析

针对自然循环工况下,蒸汽发生器部分倒U型管内存在倒流现象,利用无量纲分析方法建立管内流体控制方程,提出了阻力数和传热数等无量纲准则,并对蒸汽发生器倒U型管倒流的影响因素进行分析。结果表明,阻力数对倒流发生的无量纲进出口压降和流速有较大的影响;传热数对倒流发生的无量纲进出口压降有较大的影响,而对流速影响较小。     

Detailed Evaluation of the Natural Circulation Mass Flow Rate of Water Propelled by Using an Air Injection

One-dimensional (1D) air-water two-phase natural circulation flow in the “thermohydraulic evaluation of reactor cooling mechanism by external self-induced flow—one-dimensional” (THERMES-1D) experiment has been verified and evaluated by using the RELAP5/MOD3 computer code. Experimental results on the 1D natural circulation mass flow rate of water propelled by using an air injection have been evaluated in detail. The RELAP5 results have shown that an increase in the air injection rate to 50% of the total heat flux leads to an increase in the water circulation mass flow rate. However, an increase in the air injection rate from 50 to 100% does not affect the water circulation mass flow rate, because of the inlet area condition. As the height increases in the air injection part, the void fraction increases. However, the void fraction in the upper part of the air injector maintains a constant value. An increase in the air injection mass flow rate leads to an increase in the local void fraction, but it has no influence on the local pressure. An increase in the coolant inlet area leads to an increase in the water circulation mass flow rate. However, the water outlet area does not have an influence on the water circulation mass flow rate. As the coolant outlet moves to a lower position, the water circulation mass flow rate decreases.     

Sub- to Supercritical Flow Transition in a Horizontally-Stratified Two-Phase Flow in PWR Hot Legs

A co-current, horizontally-stratified, two-phase flow would appear in the hot legs of a pressurized water reactor during a certain class of small-break loss-of-coolant accident. The liquid velocity in the hot leg may become so high that it exceeds the speed of interfacial waves. The condition for the onset of such a “supercritical” flow is studied in this paper by analyzing experimental data taken in the ROSA-IV Large Scale Test Facility. It is shown that the energy loss at the hot leg inlet needs to be taken into account to predict the above onset condition reasonably well.     

细长自然循环系统流动不稳定性实验研究

以水为工质,在常压下对拥有细长回路和较长水平段的自然循环系统进行可视化实验研究,并以典型的实验现象（ P =1.46 kW）为例分析该系统的瞬态运行特性和不稳定性机理。结果表明：阻力系数较大的细长自然循环回路难以产生有效的单相自然循环,只能通过间歇性沸腾和两相流动将热量导出。这是因当回路阻力较大时,过冷沸腾产生的驱动力无法驱动回路产生有效的自然循环,而只有当加热段内流体发生饱和沸腾时才能驱动系统产生循环流动。较大的回路阻力和沸腾过程中产生的系统降压闪蒸是细长自然循环系统难以维持稳定的流动驱动压头从而产生间歇性沸腾和强烈流动不稳定性的根本原因。     

自然循环反应堆流量分配优化研究

由于自然循环反应堆一回路产生的驱动力有限,回路循环总流量较小,因此堆芯流量分配设计与优化非常重要.合理的堆芯流量分配不仅能满足热工安全要求,还能直接提高堆芯的性能.基于以上原因,本文对自然循环反应堆流量分配优化问题进行了初步研究,对闭式并联通道,采用一维流动传热模型,建立了入口阻力系数优化初值求解模型并设计了精确解搜索...     

HFETR流量反转分析研究

中国高通量工程试验堆（HFETR）在流量反转过程中,堆芯热工参数的变化会影响到反应堆的安全运行。为此本文利用RELAP5/MOD3程序建立了HFETR模型,进行了相关的研究,得出HFETR强迫循环向自然循环转换的最大允许功率为850kW,自然循环向强迫循环过渡的时刻由压力壳上部水温决定。研究结果表明,现运行模式能保证反应堆的运行安全,为以后运行模式的完善提供了支持。